Neutron embrittlement and thermal annealing of low alloy nuclear reactor pressure vessel steels and welds: A mechanisms overview and practical aspects

Conference · Thu Sep 01 04:00:00 EDT 1994

OSTI ID:50694

Tipping, P ^[1]

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1. Paul Scherrer Institut, Villigen PSI (Switzerland)

Irradiating low alloy ferritic reactor pressure vessel (RPV) steels and weldments with high energy neutrons is not without consequence; it can cause changes in both mechanical and physical properties. The degree of change invoked depends on many factors including alloy composition, heat treatment, irradiation temperature and, especially for the case of weldments, the type of welding flux used and the amount of impurity copper present. The metallurgical aspects concerned with the causes of embrittlement and the processes which are likely to occur during an annealing operation to mitigate it are addressed. Some results of annealing trials are presented; they underline the potential of annealing for restoring mechanical properties.

• Research Organization: Sandia National Labs., Albuquerque, NM (United States)
• OSTI ID: 50694
• Report Number(s): SAND--94-1515/2; CONF-9402110--Vol.2; ON: DE95002787
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
ANNEALING
EMBRITTLEMENT
LOW ALLOY STEELS
PWR TYPE REACTORS
REACTOR VESSELS